CA2818881C - Modele d'evaluation complete et methodologie d'analyse d'un accident par defaut de refroidissement - Google Patents

Modele d'evaluation complete et methodologie d'analyse d'un accident par defaut de refroidissement Download PDF

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Publication number
CA2818881C
CA2818881C CA2818881A CA2818881A CA2818881C CA 2818881 C CA2818881 C CA 2818881C CA 2818881 A CA2818881 A CA 2818881A CA 2818881 A CA2818881 A CA 2818881A CA 2818881 C CA2818881 C CA 2818881C
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break
uncertainty
values
coolant accident
loss
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CA2818881A1 (fr
Inventor
Cesare Frepoli
Katsuhiro Ohkawa
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Westinghouse Electric Co LLC
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Westinghouse Electric Co LLC
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Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/001Computer implemented control
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/04Safety arrangements
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Business, Economics & Management (AREA)
  • Emergency Management (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

La présente invention concerne un système et un procédé informatisés permettant d'effectuer une analyse de sûreté en prenant comme postulat un accident par défaut de refroidissement (LOCA) dans un réacteur nucléaire, pour une gamme complète de tailles de fracture, notamment des petites fractures, des fractures intermédiaires et des grandes fractures. En outre, la modélisation et l'analyse des accidents par défaut de refroidissement postulés dus à des petites fractures, des fractures intermédiaires et des grandes fractures sont effectuées avec un seul code informatique et un seul modèle d'entrée correctement validés par rapport à des données expérimentales pertinentes. Les incertitudes d'entrée et de modèle physique sont combinées selon un processus d'échantillonnage aléatoire, par exemple selon une approche de Monte Carlo direct (ASTRUM-FS) et des procédures statistiques avancées sont utilisées pour se conformer aux critères 10 CFR 50.46 de la commission de régulation nucléaire.
CA2818881A 2010-11-23 2011-11-23 Modele d'evaluation complete et methodologie d'analyse d'un accident par defaut de refroidissement Active CA2818881C (fr)

Applications Claiming Priority (5)

Application Number Priority Date Filing Date Title
US41637110P 2010-11-23 2010-11-23
US61/416,371 2010-11-23
US13/303,188 US9208911B2 (en) 2010-11-23 2011-11-23 Full spectrum LOCA evaluation model and analysis methodology
PCT/US2011/061987 WO2012071483A2 (fr) 2010-11-23 2011-11-23 Modèle d'évaluation complète et méthodologie d'analyse d'un accident par défaut de refroidissement
US13/303,188 2011-11-23

Publications (2)

Publication Number Publication Date
CA2818881A1 CA2818881A1 (fr) 2012-05-31
CA2818881C true CA2818881C (fr) 2019-06-11

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CA2818881A Active CA2818881C (fr) 2010-11-23 2011-11-23 Modele d'evaluation complete et methodologie d'analyse d'un accident par defaut de refroidissement

Country Status (5)

Country Link
US (1) US9208911B2 (fr)
CN (1) CN103548093B (fr)
CA (1) CA2818881C (fr)
WO (1) WO2012071483A2 (fr)
ZA (1) ZA201304378B (fr)

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WO2014059057A1 (fr) 2012-10-09 2014-04-17 Avery Dennison Corporation Adhésifs et procédés associés
CN104462623A (zh) * 2013-09-12 2015-03-25 中国核动力研究设计院 一种反应堆冷却剂系统loca分析模型快速建立方法
CN107207924B (zh) 2015-02-05 2020-03-13 艾利丹尼森公司 恶劣环境用标签组件
US10990714B2 (en) 2015-12-22 2021-04-27 Bwxt Mpower, Inc. Apparatus and method for safety analysis evaluation with data-driven workflow
US10526511B2 (en) 2016-12-22 2020-01-07 Avery Dennison Corporation Convertible pressure sensitive adhesives comprising urethane (meth)acrylate oligomers
US11170073B2 (en) * 2017-08-24 2021-11-09 Westinghouse Electric Company Llc Sequential embedding statistical analysis for multidimensional tolerance limits
CN111125972B (zh) * 2019-12-26 2021-10-19 西安交通大学 核电厂破口失水事故水力载荷分析方法
CN111144752B (zh) * 2019-12-26 2022-04-05 西安交通大学 基于遗传算法的核电厂失水事故安注流量需求分析方法
CN111695762B (zh) * 2020-04-29 2023-05-05 中国核电工程有限公司 核事故扩散结果的修正方法、装置及后果评价方法、系统
CN111554425B (zh) * 2020-05-15 2022-02-11 中国核动力研究设计院 一种压水堆核电厂极小破口失水事故应对方法
CN113191425A (zh) * 2021-04-28 2021-07-30 上海核工程研究设计院有限公司 一种泄漏点数据模型的建立方法、漏点识别方法、识别装置
CN113191556A (zh) * 2021-05-08 2021-07-30 上海核工程研究设计院有限公司 一种核电Loca事件故障预测与诊断方法
CN113536537B (zh) * 2021-06-10 2024-01-12 中国核动力研究设计院 一种大破口失水事故分析方法及系统
CN113948231B (zh) * 2021-09-09 2023-08-08 国家电投集团科学技术研究院有限公司 核电厂小破口事故的关键现象的识别方法及装置
CN113761749B (zh) * 2021-09-10 2022-03-22 哈尔滨工程大学 核反应堆概率安全裕度分析方法、系统、终端及存储介质
CN114638081B (zh) * 2021-11-11 2023-03-24 国家电投集团科学技术研究院有限公司 核电设计软件模型评估系统
CN115099040B (zh) * 2022-06-29 2023-09-29 中国人民解放军91439部队 一种板状结构网格模型破口面积计算方法及系统
CN115048809B (zh) * 2022-07-11 2023-08-29 中国核动力研究设计院 一种用于多物理多尺度耦合系统的不确定性量化方法
CN115266794B (zh) * 2022-07-29 2024-06-04 中国核动力研究设计院 一种loca高温辐照后uo2气孔演变行为获取方法
CN116305837B (zh) * 2023-02-16 2024-02-02 华中科技大学 一种突出比例分析的模块化不确定性量化评估方法及设备

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US5009833A (en) * 1989-01-11 1991-04-23 Westinghouse Electric Corp. Expert system for surveillance, diagnosis and prognosis of plant operation
KR100681487B1 (ko) * 2002-10-30 2007-02-09 한국전력공사 원자력발전소 안전해석을 위한 최적평가체계
US8873698B2 (en) 2002-12-18 2014-10-28 Global Nuclear Fuel—Americas, LLC Computer-implemented method and system for designing a nuclear reactor core which satisfies licensing criteria
DE10334580B3 (de) * 2003-07-28 2005-03-17 Framatome Anp Gmbh Brennelement für einen Druckwasserkernreaktor
US8109766B2 (en) * 2003-10-03 2012-02-07 Global Nuclear Fuel-Americas Llc Method for predicted reactor simulation
US7426458B2 (en) * 2004-12-30 2008-09-16 Global Nuclear Fuel - Americas, Llc Nuclear reactor reload licensing analysis system and method
RU2005116169A (ru) * 2005-05-20 2006-11-27 Вадим Игоревич Дунаев (RU) Способ и система анализа и оценки безопасности технологического процесса
US7860207B2 (en) * 2006-11-28 2010-12-28 The Invention Science Fund I, Llc Method and system for providing fuel in a nuclear reactor
US7685079B2 (en) 2006-12-21 2010-03-23 Global Nuclear Fuel - Americas, Llc Methods for evaluating robustness of solutions to constraint problems
US20080154638A1 (en) * 2006-12-22 2008-06-26 Coyle Carl M Method and system for providing cross-systems services to developmentally disabled youth
US9502145B2 (en) * 2009-09-23 2016-11-22 Terrapower, Llc Nuclear reactor operation and simulation

Also Published As

Publication number Publication date
ZA201304378B (en) 2014-02-26
CN103548093A (zh) 2014-01-29
US20120185222A1 (en) 2012-07-19
CA2818881A1 (fr) 2012-05-31
WO2012071483A2 (fr) 2012-05-31
WO2012071483A3 (fr) 2013-09-19
CN103548093B (zh) 2016-08-10
US9208911B2 (en) 2015-12-08

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